US5372794A - Process for the separation of certain elements from aqueous solutions resulting from the reprocessing of spent nuclear fuels - Google Patents

Process for the separation of certain elements from aqueous solutions resulting from the reprocessing of spent nuclear fuels Download PDF

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US5372794A
US5372794A US08/025,856 US2585693A US5372794A US 5372794 A US5372794 A US 5372794A US 2585693 A US2585693 A US 2585693A US 5372794 A US5372794 A US 5372794A
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process according
aqueous solution
ruthenium
solution
resin
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Marc Lemaire
Jacques Foos
Alain Guy
Micheline Draye
Rodolph Chomel
Rene Chevillotte
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Orano Cycle SA
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Compagnie Generale des Matieres Nucleaires SA
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Assigned to COMPAGNIE GENERALE DES MATIERES NUCLEAIRES reassignment COMPAGNIE GENERALE DES MATIERES NUCLEAIRES ASSIGNMENT OF ASSIGNORS INTEREST. Assignors: CHEVILLOTTE, RENE, CHOMEL, RODOLPH, DRAYE, MICHELINE, FOOS, JACQUES, GUY, ALAIN, LEMAIRE, MARC
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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/42—Reprocessing of irradiated fuel
    • G21C19/44—Reprocessing of irradiated fuel of irradiated solid fuel
    • G21C19/46—Aqueous processes, e.g. by using organic extraction means, including the regeneration of these means
    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22B—PRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
    • C22B11/00—Obtaining noble metals
    • C22B11/04—Obtaining noble metals by wet processes
    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22B—PRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
    • C22B3/00—Extraction of metal compounds from ores or concentrates by wet processes
    • C22B3/20—Treatment or purification of solutions, e.g. obtained by leaching
    • C22B3/42—Treatment or purification of solutions, e.g. obtained by leaching by ion-exchange extraction
    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22B—PRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
    • C22B59/00—Obtaining rare earth metals
    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22B—PRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
    • C22B60/00—Obtaining metals of atomic number 87 or higher, i.e. radioactive metals
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02P—CLIMATE CHANGE MITIGATION TECHNOLOGIES IN THE PRODUCTION OR PROCESSING OF GOODS
    • Y02P10/00—Technologies related to metal processing
    • Y02P10/20—Recycling
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02W—CLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT
    • Y02W30/00—Technologies for solid waste management
    • Y02W30/50—Reuse, recycling or recovery technologies

Definitions

  • the present invention relates to a process for the separation of at least one element such as Nb, Sb, Ce+Pr, actinides and elements from groups VIIb (Mn, Tc, Re) and VIII (Fe, Co, Ni, Ru, Rh, Pd, Os, Ir, Pt) of the Periodic Classification of Elements present in an aqueous solution resulting from the reprocessing of spent nuclear fuels.
  • groups VIIb Mn, Tc, Re
  • VIII Fe, Co, Ni, Ru, Rh, Pd, Os, Ir, Pt
  • the low activity effluents i.e. whose specific activity ⁇ does not exceed 0.37GBq/m 3 (or 10 -2 Ci/m 3 ) for elements other than 137 Cs and 90 Sr, generally contain manganese antimony, ruthenium, cesium and cobalt in radioactive form.
  • the average or moderate activity effluents with a specific activity ⁇ between 0.37 and 37GBq/m 3 (or between 10 -2 and 1Ci/m 3 ) e.g. contain manganese, ruthenium, cobalt, cesium, cerium and praseodymium in radioactive form.
  • the high activity effluents i.e.
  • ⁇ between 37GBq/m 3 and 1.8TBq/m 3 (or between 1 and 50Ci/m 3 )
  • the average and high activity effluents also have an activity between 10 -5 and 3.10 -2 mCi/1, due to the presence of elements such as Pu, Am and Cm.
  • the dissolving solutions for spent nuclear fuels are generally nitric solutions incorporating actinides, numerous metals and substantially all the fission products, particularly ruthenium 106, cesium 137 and 134, antimony 125, europium 154, cerium and praseodymium 144.
  • the fission product concentrates which are nitric solutions obtained after the separation of uranium and plutonium from the spent nuclear fuel dissolving solutions, incorporate numerous elements including in particular iron, nickel, molybdenum, copper, ruthenium, rhodium and technetium.
  • one of the aims of the invention is to separate certain elements present in these effluents or solutions.
  • these elements are in particular metals from the platinum group such as palladium, rhodium and ruthenium, which are valorizable elements, particularly rhodium due to its use in catalytic converters for the car industry. It would also be of interest to have processes making it possible to permit the effective separation of ruthenium, rhodium and palladium.
  • Nb, Sb and metals of groups VIIb and VIII to be recovered are very low compared with those of the other elements present in the solution, such as uranium and plutonium in the case of dissolving solutions and sodium in the case of certain aqueous effluents.
  • the present invention specifically relates to a process for the separation of at least one element chosen from among Nb, Sb, actinides, Ce, Pr and elements of group VIIb and group VIII, which has the advantage of being easy to perform, being applicable to different effluent types and leading to high recovery yields.
  • the process for the separation of at least one element chosen from among Nb, Sb, actinides, Ce+Pr and elements of groups VIIb and VIII of the Periodic Classification of Elements, present in an aqueous solution resulting from the reprocessing of spent nuclear fuels consists of contacting said aqueous solution with a solid resin based on vinyl pyridine polymer or copolymer and separating from said solution the resin which has fixed at least one of the said elements.
  • the use of a solid resin based on vinyl pyridine polymer or copolymer is very advantageous, because said resin has a very good affinity for Nb, Sb, actinides, Ce+Pr and group VIIb and VIII elements. Moreover, these resins have a good thermal stability and a good oxidation resistance and can be used in an acid medium, particularly a nitric medium.
  • the polyvinyl pyridine resin becomes less effective due to a saturation by the separated elements, it is possible to regenerate it by washing it with water, an acid solution, e.g. 0.1 to 4M HNO 3 , or an alkaline solution, e.g. 0.1M NH 4 OH.
  • an acid solution e.g. 0.1 to 4M HNO 3
  • an alkaline solution e.g. 0.1M NH 4 OH.
  • the vinyl pyridine polymers used can e.g. be poly-2-(vinyl pyridine) or poly-4-(vinyl pyridine).
  • the vinyl pyridine copolymers which can be used are e.g. copolymers of vinyl pyridine and divinyl benzene.
  • poly-4-(vinyl pyridine) in accordance with the formula: ##STR1## which can be crosslinked by divinyl benzene.
  • This resin which is generally marketed in basic form, can be used in a saline acid medium, e.g. in the form: ##STR2## with A- representing an anion such as NO 3 - or Cl-.
  • the resin is generally in the form of a powder, whose grain size is chosen by the user as a function of his needs.
  • the starting aqueous solutions are nitric solutions, which preferably have a nitric acid concentration between 10 -7 and 4 mole/l and they are contacted with the solid resin for between 1 min and 24 h.
  • the resin quantities used more particularly depend on the contents of the elements to be extracted. In general, use is made of 10 to 500 g of resin per liter of aqueous solution.
  • the process according to the invention can in particular be used for extracting ruthenium, rhodium and/or palladium from aqueous solutions resulting from the reprocessing of spent nuclear fuels.
  • the nitric acid concentration of the aqueous solution is at the most equal to 1 mole/l, preferably 10 -7 to 0.1 mole/l and the contacting of this solution with the resin takes place for between 10 and 60 min.
  • the extraction kinetics can be improved by adding chloride ions to the aqueous solution.
  • the aqueous solution preferably has a nitric acid concentration of 1 to 2 mole/l and contacting of the solution with the resin takes less than 10 min.
  • the process according to the invention can be used for treating different types of effluents and solutions resulting from the reprocessing of spent nuclear fuels.
  • it can be used for separating ruthenium, niobium, antimony, manganese, cobalt, cerium, praesodymium, plutonium, curium and americium from average and high activity effluents; for separating Fe, Ni, Rh, Ru, Co and Tc from fission product concentrates; and for separating Pd, Ru, Rh, Tc, Co, Ni, Fe from irradiated fuel dissolving solutions.
  • FIG. 1 A diagram showing the ruthenium extraction level variations (as a %) as a function of the pH of the aqueous starting solution.
  • FIGS. 2 to 5 Diagrams illustrating the percentages of reextracted elements as a function of the treated effluent volume.
  • the ruthenium is extracted from an aqueous effluent highly charged with salts, which contains 1.38 mole/l of HNO 3 , 2 g/l of Na + , 6 mg/l of K + and 1 mg/l of ruthenium.
  • contacting takes place under magnetic stirring and for 20.5 h of 1 g of poly-4-(vinyl pyridine) and 40 ml of aqueous solution containing 1 mg/l of ruthenium.
  • the resin is then separated from the solution on a paper filter and the residual ruthenium in the solution is dosed by a plasma torch. This gives a ruthenium extraction rate of 66.5%, which corresponds to 2.66.10 -2 mg of ruthenium per gramme of resin.
  • the dosing of sodium and potassium in the filtered solution indicates that they have not been extracted by the resin.
  • polyvinyl pyridine makes it possible to obtain a 100% extraction rate for ruthenium in the case of very low ruthenium contents and even when there are high sodium and potassium contents.
  • the ruthenium is extracted from an aqueous solution having a nitric acid concentration of 1.38 mole/l and which contains 0.5 mg/l of ruthenium, 2 g/l of sodium and 6 mg/l of potassium and to which is added sodium chloride in order to have a sodium chloride concentration of 1 mole/l.
  • the ruthenium is separated from effluents containing sodium and potassium and the influence of the pH on the extraction rate is studied. To this end contacting takes place between 10 ml of solution containing traces of Ru, 6 mg/l of potassium and 2 g/l of sodium and having nitric acid concentrations corresponding to pH-values between 3 and 9 with approximately 0.2 g of poly-4-(vinyl pyridine), accompanied by stirring for 1 h.
  • the resin is then separated on a paper filter and the residual ruthenium is dosed in the solution by a plasma torch.
  • the attached drawing shows the ruthenium extraction rate and the ruthenium quantity fixed per gramme of resin as a function of the pH of the solution. It can be seen that the ruthenium is extracted more efficiently for acid pH-levels below 6, i.e. nitric acid concentrations above 10 -6 mole/l.
  • rhodium is extracted from aqueous solutions containing approximately 2 mmole/l of rhodium and having nitric acid concentrations as given in table 2.
  • extraction takes place of the palladium present in an aqueous solution containing approximately 1 mmole/l of palladium and 1.38 mole/l of nitric acid by contacting 10 ml of solution with polyvinyl pyridine quantities corresponding to concentrations of 2 to 40 g/l for 24 h and accompanied by horizontal stirring.
  • the polyvinyl pyridine is then separated on a paper filter and the residual palladium is determined by atomic absorption.
  • the polyvinyl pyridine quantities used and the results obtained are given in table 4.
  • separation takes place of the ruthenium present in high activity effluents having a nitric acid concentration of 0.6 mole/l and containing, apart from the ruthenium, cesium 137 and cesium 134.
  • To carry out the extraction contacting takes place under mechanical stirring of 3 ml of effluent and 200 mg of poly-4-(vinyl pyridine) (PVP) for 75 min.
  • PVP poly-4-(vinyl pyridine)
  • contacting takes place of 3 ml of medium activity effluent (MA) with the composition given in table 6 and different weights of polyvinyl pyridine crosslinked by 2% divinyl benzene for 40 min and accompanied by stirring.
  • the nitric acidity of the effluent is 0.1 mole/l.
  • the polyvinyl pyridine is separated from the effluent and the ruthenium, manganese, cobalt, cesium and cerium+praseodymium 144 concentrations of the separated effluent are determined. The results obtained are given in table 6.
  • this table shows that it is possible to effectively eliminate the ruthenium, manganese, cobalt, cerium and praseodymium from medium activity effluents, but the cesium is not extracted.
  • EXAMPLE 24 EXTRACTION OF RUTHENIUM, NIOBIUM AND ANTIMONY
  • ruthenium, niobium and antimony are extracted from high activity (HA) effluents having the HNO 3 composition and concentration given in Table 7.
  • extraction takes place of ruthenium from an effluent concentrated by evaporation and having the composition given in table 8.
  • contacting takes place between 200 mg of polyvinyl-4-pyridine for 75 min with 3 ml of effluent, followed by the separation of the polyvinyl pyridine by filtration and the determination of the ruthenium and cesium contents of the effluent. The results obtained are also given in table 8.
  • EXAMPLE 26 SEPARATION OF TECHNETIUM, RUTHENIUM, RHODIUM, IRON, NICKEL AND COBALT
  • contacting takes place between 2 ml of concentrate and 1 g of polyvinyl pyridine (PVP) for 4 h 15 min, accompanied by mechanical stirring and in 5 min sequences.
  • PVP polyvinyl pyridine
  • the polyvinyl pyridine is filtered a first time and is then washed with 18 ml of 1N nitric acid, followed by the filtering of the resin a second time, which is then dissolved hot in 15 ml of sulphuric acid.
  • the solution obtained after the first filtration and the resin dissolving solution are analyzed by gamma spectrometry, alpha spectrometry and atomic emission spectrometry (ICP).
  • the resin leads to a very good extraction of technetium, ruthenium, rhodium, iron, nickel and cobalt with a good selectivity with respect to alkali metals, alkaline earth metals and actinides.
  • Table 10 gives the distribution of metal cations in % by weight in the fission product concentrate and on PVP resin.
  • This table demonstrates the interest of using polyvinyl pyridine for separating metals of groups VIIb and VIII.
  • the fixed cations can then be recovered in aqueous solution, if desired, by dissolving the resin in H 2 SO 4 .
  • EXAMPLE 27 SEPARATION OF TECHNETIUM, RUTHENIUM, RHODIUM, PALLADIUM, IRON AND NICKEL
  • extraction takes place of technetium, ruthenium, rhodium, palladium, iron and nickel from irradiated dissolving solutions by contacting 1 g of polyvinyl pyridine with 10 ml of dissolving solution, accompanied by mechanical stirring and for 75 min. After contacting, the resin is filtered a first time and the solution analyzed by gamma spectrometry and atomic emission spectrometry (ICP) in order to determine the contents thereof in palladium, ruthenium, rhodium, technetium, nickel and iron.
  • ICP atomic emission spectrometry
  • the decontamination factors are 1.1.10 -6 for uranium, 317 for plutonium and 874 for gamma emitters (Ru 106 deduced), which is very satisfactory.
  • the results of the first two examples demonstrate that the polyvinyl pyridine resin does not extract the alkali metals and alkaline earth metals, as well as the trivalent metals, does not extract or only very slightly extracts transuranium elements, but leads to a very good extraction of transition metals.
  • the effectiveness of the resin decreases when the salt charge increases.
  • the salt charge is close to 200 g/l and the polyvinyl pyridine exchange capacity is under the operating conditions used equal to 3.1 mg of palladium/g of resin, 0.8 mg of rhodium/g of resin, 1.6 mg of ruthenium/g of resin and above 0.034 mg of technetium/g of resin.
  • the salt charge is close to 100 g/l and the resin exchange capacity is, under these conditions, 0.7 mg Rh/g of resin, 3 mg Ru/g of resin and 1.4 mg Tc/g of resin.
  • contacting takes place between 3 ml of average or medium activity effluent having the composition given in table 13 and a nitric acid concentration of 5.10 -3 mole/l with 67 g/l of polyvinyl pyridine (200 mg) for 30 min and accompanied by stirring.
  • concentrations of plutonium, americium, curium and fission products of the separated effluent are determined.
  • the results obtained are given in table 13.
  • decontamination takes place of an average or medium activity effluent having the composition given in table 14 and operating in the following way.
  • the effluent is made to circulate in a column having an internal diameter of 0.8 cm and containing 1 g of polyvinyl pyridine, which corresponds to a polyvinyl pyridine height of 4.7 cm, the effluent being supplied under low pressure at the top of the column and using a metering pump with a delivery of 3 ml/min.
  • a metering pump with a delivery of 3 ml/min.
  • the treated effluent is collected at the bottom of the column and it is analyzed to determine the elements contained therein, using atomic emission spectrometry in the case of elements present in a weight quantity, gamma spectrometry in the case of gamma emitter radioelements and alpha spectrometry in the case of alpha emitted radioelements.
  • FIGS. 2 and 3 show the gamma emitter percentages (Ru106, Co60, Ce+Pr144 and Cs137) extracted as a function of the effluent volume treated (in ml).
  • FIG. 3 shows the alpha emitter percentages (total Pu, Am241 and Cm244) extracted as a function of the treated effluent volume (in ml).
  • FIG. 4 shows the gamma emitter element percentages (Ru106, Co60, Ce+Pr144 and Cs137) extracted as a function of the treated effluent volume (in ml).
  • FIG. 5 gives the alpha emitter percentages (total Pu, Am241 and Cm244) extracted as a function of the treated effluent volume (in ml).
  • the PVP is washed by H 2 O, 0.1M NH 4 OH, 0.1M NH 4 OH+0.1M NaClO, 0.1M HNO 3 or 4M HNO 3 , using a washing solution quantity such that it corresponds to the PVP concentrations in the washing solution given in table 15. This is followed by a determination of the Ru, Cs, Co, Mn, Ce+Pr, Sr and Pu contents in the washing solution.
  • polyvinlyl pyridine After washing the thus washed polyvinlyl pyridine is used for treating a further medium activity effluent quantity carrying out the same contacting for 30 min and using an effluent quantity such that it corresponds to the PVP concentrations given in table 15. This is followed by the determination of the Ru, Cs, Co, Mn, Ce+Pr, Sr and Pu contents of the treated effluent. The results obtained are given as extraction percentages in table 15.

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US08/025,856 1992-03-03 1993-03-03 Process for the separation of certain elements from aqueous solutions resulting from the reprocessing of spent nuclear fuels Expired - Lifetime US5372794A (en)

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FR9202516A FR2688336B1 (fr) 1992-03-03 1992-03-03 Procede pour separer le niobium, l'antimoine et/ou au moins un element des groupes viib et viii a partir de solutions aqueuses issues du retraitement des combustibles nucleaires uses.
FR9202516 1992-03-03

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JP (1) JP3241475B2 (sh)
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CN (1) CN1078923A (sh)
CA (1) CA2090812A1 (sh)
CZ (1) CZ29393A3 (sh)
DE (1) DE69306281T2 (sh)
FI (1) FI930921A (sh)
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US5499276A (en) * 1993-10-06 1996-03-12 Doryokuro Kakunenryo Kaihatsu Jigyodan Method for minor actinide nuclides incineration
US5613186A (en) * 1996-01-11 1997-03-18 General Electric Company Method for monitoring the ADU process for technetium
US5752206A (en) * 1996-04-04 1998-05-12 Frink; Neal A. In-situ decontamination and recovery of metal from process equipment
WO2001049389A1 (en) * 2000-01-03 2001-07-12 Hydromatix, Inc. Method and apparatus for metal removal by ion exchange
FR2813208A1 (fr) * 2000-08-30 2002-03-01 Commissariat Energie Atomique Structure complexante, dispositif et procede de traitement d'effluents liquides
US7097747B1 (en) 2003-08-05 2006-08-29 Herceg Joseph E Continuous process electrorefiner
US20070034573A1 (en) * 2001-01-03 2007-02-15 Juzer Jangbarwala Method and apparatus for metal removal by ion exchange
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US11319613B2 (en) 2020-08-18 2022-05-03 Enviro Metals, LLC Metal refinement
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US5604264A (en) * 1995-04-03 1997-02-18 Reilly Industries, Inc. Polyvinylpyridinium anion-exchangers for recovery of technetium and plutonium anions
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WO2002018050A1 (fr) * 2000-08-30 2002-03-07 Commissariat A L'energie Atomique Structure complexante, dispositif et procede de traitement d'effluents liquides
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US9865367B2 (en) 2012-12-21 2018-01-09 Triumf, A Joint Venture Process and apparatus for separation of technetium-99M from molybdate
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DE69306281D1 (de) 1997-01-16
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TW274140B (sh) 1996-04-11
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FI930921A0 (fi) 1993-03-02
CN1078923A (zh) 1993-12-01

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